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b5939094 |
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| 005 |
20080212000000.0 |
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m d f |
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100524e19940601dcu st f0|||||eng|d |
| 035 |
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|a (TOE)ost10176796
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| 035 |
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|a (TOE)10176796
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| 040 |
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|a TOE
|c TOE
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| 049 |
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|a GDWR
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|a 12
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0 |
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|a E 1.99:wsrc-tr--90-539-rev.3
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| 086 |
0 |
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|a E 1.99:wsrc-tr--90-539-rev.3
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| 245 |
0 |
0 |
|a Nuclear waste glass product consistency test (PCT)
|h [electronic resource] :
|b Version 7.0. Revision 3.
|
| 260 |
|
|
|a Washington, D.C. :
|b United States. Dept. of Energy ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1994.
|
| 300 |
|
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|a 50 p. :
|b digital, PDF file.
|
| 336 |
|
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|a text
|b txt
|2 rdacontent.
|
| 337 |
|
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|a computer
|b c
|2 rdamedia.
|
| 338 |
|
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|a online resource
|b cr
|2 rdacarrier.
|
| 500 |
|
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
|
| 500 |
|
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|a 06/01/1994.
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| 500 |
|
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|a "wsrc-tr--90-539-rev.3"
|
| 500 |
|
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|a "DE94017541"
|
| 500 |
|
|
|a Jantzen, C.M.; Ramsey, W.G.; Bibler, N.E.; Beam, D.C.
|
| 513 |
|
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|a Topical;
|b 06/01/1994.
|
| 520 |
3 |
|
|a Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be produced in the Defense Waste Processing Facility (DWPF), poured into stainless steel canisters, and eventually disposed of in a geologic repository. In order to comply with the Waste Acceptance Product Specifications (WAPS), the durability of the glass needs to be measured during production to assure its long term stability and radionuclide release properties. A durability test, designated the Product Consistency Test (PCT), was developed for DWPF glass in order to meet the WAPS requirements. The response of the PCT procedure was based on extensive testing with glasses of widely different compositions. The PCT was determined to be very reproducible, to yield reliable results rapidly, and to be easily performed in shielded cell facilities with radioactive samples. Version 7.0 of the PCT procedure is attached. This draft version has been submitted to ASTM for full committee (C26, Nuclear Fuel Cycle) ballot after being balloted successfully through subcommittee C26.13 on Repository Waste Package Materials Testing.
|
| 536 |
|
|
|b AC09-89SR18035.
|
| 650 |
|
7 |
|a High-level Radioactive Wastes.
|2 local.
|
| 650 |
|
7 |
|a Radioactive Waste Processing.
|2 local.
|
| 650 |
|
7 |
|a Destructive Testing.
|2 local.
|
| 650 |
|
7 |
|a Crushing.
|2 local.
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| 650 |
|
7 |
|a Leaching.
|2 local.
|
| 650 |
|
7 |
|a Materials Testing.
|2 local.
|
| 650 |
|
7 |
|a Savannah River Plant.
|2 local.
|
| 650 |
|
7 |
|a Borosilicate Glass.
|2 local.
|
| 650 |
|
7 |
|a Vitrification.
|2 local.
|
| 650 |
|
7 |
|a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.
|2 edbsc.
|
| 710 |
2 |
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|a Westinghouse Savannah River Company.
|4 res.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|4 spn.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|b Savannah River Site.
|4 res.
|
| 710 |
1 |
|
|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
|
| 856 |
4 |
0 |
|u http://www.osti.gov/servlets/purl/10176796-8GjPtv/native/
|z Online Access
|
| 907 |
|
|
|a .b59390943
|b 03-06-23
|c 05-24-10
|
| 998 |
|
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|a web
|b 05-24-10
|c f
|d m
|e p
|f eng
|g dcu
|h 0
|i 1
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|s 754a111d-d71b-5cbe-9f5b-1061e508848b
|
| 952 |
f |
f |
|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99:wsrc-tr--90-539-rev.3
|h Superintendent of Documents classification
|i web
|n 1
|
